skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Validation of the thermal transport model used for ITER startup scenario predictions with DIII-D experimental data

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [3];  [3];  [3];  [4]
  1. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); ITER Organization, St. Paul Lez Durance (France)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  3. General Atomics, San Diego, CA (United States)
  4. Oak Ridge Associated Universities (ORAU), Oak Ridge, Tennessee (United States)

We are exploring characteristics of ITER startup scenarios in similarity experiments conducted on the DIII-D Tokamak. In these experiments, we have validated scenarios for the ITER current ramp up to full current and developed methods to control the plasma parameters to achieve stability. Predictive simulations of ITER startup using 2D free-boundary equilibrium and 1D transport codes rely on accurate estimates of the electron and ion temperature profiles that determine the electrical conductivity and pressure profiles during the current rise. Here we present results of validation studies that apply the transport model used by the ITER team to DIII-D discharge evolution and comparisons with data from our similarity experiments.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC52-07NA27344; FC02-04ER54698
OSTI ID:
1239227
Report Number(s):
LLNL-JRNL-421847; TRN: US1600617
Journal Information:
Nuclear Fusion, Vol. 51, Issue 1; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 16 works
Citation information provided by
Web of Science

References (16)

Development in the DIII-D tokamak of advanced operating scenarios and associated control techniques for ITER journal September 2007
Reconstruction of current profile parameters and plasma shapes in tokamaks journal November 1985
ITER shape controller and transport simulations journal April 2008
TSC simulation of Ohmic discharges in TFTR journal March 1993
Full tokamak discharge simulation of ITER by combining DINA-CH and CRONOS journal September 2009
Microinstability-based model for anomalous thermal confinement in tokamaks journal December 1986
Development of ITER 15 MA ELMy H-mode inductive scenario journal July 2009
ITER startup studies in the DIII-D tokamak journal November 2008
Bootstrap current and neoclassical transport in tokamaks of arbitrary collisionality and aspect ratio journal September 1997
Pressure and inductance effects on the vertical stability of shaped tokamaks journal May 1993
Experimental studies of ITER demonstration discharges journal July 2009
Motional Stark effect diagnostic expansion on DIII-D for enhanced current and Er profile measurements journal October 2006
Chapter 8: Plasma operation and control journal June 2007
Chapter 1: Overview and summary journal June 2007
Experimental simulation of ITER rampdown in DIII-D journal March 2010
Chapter 4: Power and particle control journal June 2007

Cited By (3)

Integrated modeling of plasma ramp-up in DIII-D ITER-like and high bootstrap current scenario discharges journal April 2018
Gyrokinetic GENE simulations of DIII-D near-edge L-mode plasmas journal September 2019
Gyrokinetic GENE simulations of DIII-D near-edge L-mode plasmas text January 2018

Similar Records

Integrated modeling of plasma ramp-up in DIII-D ITER-like and high bootstrap current scenario discharges
Journal Article · Wed Apr 25 00:00:00 EDT 2018 · Physics of Plasmas · OSTI ID:1239227

ITER startup studies in the DIII-D tokamak
Journal Article · Tue Jan 01 00:00:00 EST 2008 · Nuclear Fusion · OSTI ID:1239227

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR
Journal Article · Thu Nov 23 00:00:00 EST 2017 · Plasma Physics and Controlled Fusion · OSTI ID:1239227

Related Subjects